The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (βN ≥ 3.5) is achievable with 25 MW of NB power at IP = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at IP = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.
|ジャーナル||Fusion Engineering and Design|
|号||8-14 PART B|
|出版ステータス||出版済み - 2 2006|
|イベント||Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - |
継続期間: 5 22 2005 → 5 27 2005
All Science Journal Classification (ASJC) codes